IR 05000298/2018001
| ML18128A094 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 05/08/2018 |
| From: | Jason Kozal NRC/RGN-IV/DRP/RPB-C |
| To: | Dent J Nebraska Public Power District (NPPD) |
| Kozal J | |
| References | |
| IR 2018001 | |
| Download: ML18128A094 (34) | |
Text
May 8, 2018
SUBJECT:
COOPER NUCLEAR STATION - NRC INTEGRATED INSPECTION REPORT 05000298/2018001
Dear Mr. Dent:
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Cooper Nuclear Station. On April 16, 2018, the NRC inspectors discussed the results of this inspection with Mr. J. Kalamaja, General Manager Plant Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.
No NRC-identified or self-revealed findings were identified during this inspection.
However, inspectors documented a licensee-identified violation, which was determined to be of very low safety significance, in this report. The NRC is treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy. Jr.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Jason Kozal, Chief Project Branch C Division of Reactor Projects
Docket No. 50-298 License No. DPR-46
Enclosure:
Inspection Report 05000298/2018001 w/ Attachments:
1. Documents Reviewed 2. NRC Request for Information 3. O
Inspection Report
Docket Number:
05000298
License Number:
Report Number:
Enterprise Identifier: I-2018-001-0003
Licensee:
Nebraska Public Power District
Facility:
Cooper Nuclear Station
Location:
72676 648A Ave
Brownville, NE
Inspection Dates:
January 1, 2018 to March 31, 2018
Inspectors:
P. Voss, Senior Resident Inspector
R. Kumana, Acting Senior Resident Inspector
M. Stafford, Resident Inspector
P. Elkmann, Senior Emergency Preparedness Inspector
S. Money, Health Physicist
J. ODonnell, CHP, Health Physicist
Approved By:
J. Kozal, Branch Chief
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Cooper Nuclear Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. A licensee-identified, non-cited violation is documented in report Section 71152.
No findings were identified.
PLANT STATUS
Cooper Nuclear Station began the inspection period at rated thermal power. On February 16, 2018, the licensee reduced power to 36 percent in order to enter single loop operation to perform maintenance on reactor recirculation motor generator B, repair condenser leaks, perform maintenance on control rod drives, and tune a reactor recirculation system motor generator set. The licensee restored power to 100 percent on February 18, 2018. On March 11, 2018, the licensee performed a normal shutdown to repair a reactor coolant leak inside the drywell. The licensee restarted the reactor on March 16, 2018, and resumed full power operation on March 19, 2018. The licensee maintained full power for the remainder of the reporting period, except for minor reductions in power to support scheduled surveillances and rod pattern adjustments.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather (1 Sample)
The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures.
Impending Severe Weather (1 Sample)
The inspectors evaluated readiness for impending adverse weather conditions for a winter weather advisory on January 10, 2018.
71111.04 - Equipment Alignment
Partial Walkdown (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Division 2 residual heat removal during service water booster pump A replacement on January 12, 2018
- (2) Division 2 reactor equipment cooling during Division 1 reactor equipment cooling maintenance window on January 31, 2018
- (3) Emergency diesel generator 2 lube oil during emergency diesel generator 1 work window on February 7, 2017
- (4) Emergency diesel generator 1 starting air during emergency diesel generator 2 work window on March 22, 2018
71111.05AQ - Fire Protection Annual/Quarterly
Quarterly Inspection (4 Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Reactor building 931 foot elevation, Fire Area RB-M, Zones 3C and 3D on January 31, 2018
- (2) Emergency diesel generator 1, Fire Area DG-A, Zone 14A on February 26, 2018
- (3) Condensate pump area, turbine building 882 foot elevation, Fire Area TB-A, Zone 11J on March 20, 2018
- (4) Emergency diesel generator 2, Fire Area DG-B, Zone 14B on March 26, 2018
71111.06 - Flood Protection Measures
Internal Flooding (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the reactor building 931 foot elevation, reactor equipment cooling heat exchanger area on February 22, 2018.
71111.07 - Heat Sink Performance
Heat Sink (1 Sample)
The inspectors evaluated a residual heat removal heat exchanger thermal performance test on January 17, 2018.
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance
Operator Requalification (1 Sample)
The inspectors observed and evaluated a licensed operator requalification scenario in the simulator on January 23, 2018.
Operator Performance (1 Sample)
The inspectors observed and evaluated the quarterly downpower, including entry into single loop operations, power reduction to 45 percent, and planned trip of reactor recirculation motor generator set B and the associated pre-job briefs on February 17, 2018.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness (1 Sample)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Emergency diesel generator 2 system a(1) evaluation due to exceeding performance criteria on March 9, 2018
71111.13 - Maintenance Risk Assessments and Emergent Work Control
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Service water booster pump A replacement on January 9, 2018
- (2) Service water booster pump D maintenance window on January 17, 2018
- (3) Emergent service water valve maintenance due to reactor equipment cooling heat exchanger B leakage on January 29, 2018
- (4) Emergency diesel generator 1 work window on February 6, 2018
- (5) Reactor recirculation motor generator set maintenance and single loop operation on February 17, 2018
- (6) Emergent steam leak repair affecting high pressure coolant injection on March 8, 2018
- (7) Emergency diesel generator 2 work window on March 23, 2018
71111.15 - Operability Determinations and Functionality Assessments
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Jet pump 12 differential pressure reading step change on January 22, 2018
- (2) Reactor equipment cooling heat exchanger outlet valve SW-MO-651 indications of potential leak path on January 22, 2018
- (3) Scram discharge volume shielding evaluation on January 25, 2018
- (4) Emergency diesel generator 2 field flash resistor insulation issue and extent of condition for emergency diesel generator 1 on March 23, 2018
71111.18 - Plant Modifications
The inspectors evaluated the following temporary or permanent modifications:
- (1) Reactor equipment cooling heat exchanger B, SW-V-126 temporary flange on February 5, 2018
71111.19 - Post Maintenance Testing
The inspectors evaluated the following post maintenance tests:
- (1) Service water booster pump A replacement on January 16, 2018
- (2) Post maintenance test for emergency diesel generator 1 system maintenance on February 20, 2018
- (3) South west residual heat removal quad fan coil unit maintenance on February 23, 2018
- (4) Unplanned service water valve maintenance due to reactor equipment cooling heat exchanger B leakage on February 26, 2018
- (5) Post maintenance test for emergency diesel generator 2 system maintenance on March 23, 2018
71111.20 - Refueling and Other Outage Activities
The inspectors evaluated forced outage activities due to reactor coolant system leakage from March 12, 2018, to March 16, 2018.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Routine
- (1) Emergency diesel generator 1, 31-day operability test on January 8, 2018
- (2) Reactor recirculation motor generator set B surveillance testing on February 17, 2018
In-service (1 Sample)
- (1) Reactor core isolation cooling quarterly in-service surveillance test on March 29, 2018
Reactor Coolant System Leak Detection (1 Sample)
- (1) Drywell unidentified leakage integrator functional test and calibration on February 20, 2018
71114.04 - Emergency Action Level and Emergency Plan Changes
The inspector evaluated two submitted Emergency Action Level and Emergency Plan changes in-office on January 30, 2018, and March 12, 2018. This evaluation does not constitute NRC approval.
71114.06 - Drill Evaluation
Drill/Training Evolution (1 Sample)
The inspectors evaluated the licensed operator training scenario in the simulator control room on January 23,
RADIATION SAFETY
71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls
Radiological Work Planning (1 Sample)
The inspectors evaluated the licensees radiological work planning by reviewing the following activities:
- (1) 2016-01, refueling outage 29 control rod drive mechanism replacements
- (2) 2016-03, reactor water cleanup pump B replace power frame
- (3) 2016-05, RE-29 refuel floor activities
- (4) 2016-12, RE-29, in-service inspection and flow accelerated corrosion exams
- (5) 2016-23, reactor recirculation pump A motor, impeller, and seal
- (6) 2017-01, spent fuel pool clean-up project (Online)
Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)
The inspectors evaluated dose estimates and exposure tracking.
71124.04 - Occupational Dose Assessment
Source Term Characterization (1 Sample)
The inspectors evaluated the licensees source term characterization.
External Dosimetry (1 Sample)
The inspectors evaluated the licensees external dosimetry program.
Internal Dosimetry (1 Sample)
The inspectors evaluated the licensees internal dosimetry program.
Special Dosimetric Situations (1 Sample)
The inspectors evaluated the licensees performance for special dosimetric situations.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below.
=
- (1) IE01: Unplanned Scrams per 7000 Critical Hours Sample (January 1,2017, through December 31, 2017)
- (2) IE03: Unplanned Power Changes per 7000 Critical Hours Sample (January 1, 2017, through December 31, 2017)
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Both emergency diesel generators declared inoperable due to light bulb socket deficiencies
71153 - Follow-up of Events and Notices of Enforcement Discretion Events
The inspectors evaluated the failure of the primary alert and notification system and the licensees response on March 16,
INSPECTION RESULTS
Licensee Identified Non-Cited Violation 71152 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Title 10 CFR Part 50, Appendix B, Criterion III, Design Control, requires, in part, that for those systems, structures, and components to which this appendix applies, Design control measures shall provide for verifying or checking the adequacy of design.
Contrary to the above, between September 2003, and December 19, 2017, the licensee failed to verify or check the adequacy of design of quality-related components associated with the Division 1 and 2 emergency diesel generator 125 Vdc control power circuits. Specifically, in 2003, the licensee modified the design of the control power circuit through Part Evaluation (PE) 4222806 and replaced 24 original light bulb lamp assemblies with a different style of light bulb and a carbon film dropping resistor (vs. the original wire-wound design).
This change created an unrecognized vulnerability that left the affected portions of the circuit with dropping resistors that provided insufficient protection from shorting due to indication light bulb failures. As a result, on December 19, 2017, the licensee declared both emergency diesel generators inoperable due to the design vulnerability.
Significance/Severity Level: The finding created a design vulnerability in the emergency diesel generator control power circuits, and resulted in the Division 1 and 2 emergency diesel generators being declared inoperable at the time of discovery. Although the emergency diesel generators were declared inoperable, subsequent licensee analysis determined that the system retained its function, and maintained a reasonable expectation of operability while the design deficiencies existed. Accordingly, the inspectors assessed the significance of this finding in accordance with Inspection Manual Chapter 0609, Appendix A, The Significance Determination Process (SDP) for Findings at Power, dated June 19, 2012, and determined this finding was of very low safety significance (Green) because it was a deficiency affecting the design or qualification of a mitigating structure, system, or component (SSC), but the SSC maintained its operability.
Corrective Action Reference(s): Immediate corrective actions included compensatory measures to remove light bulbs from the vulnerable lamp assemblies in order to eliminate the shorting hazard. This issue was entered into the licensees corrective action program as Condition Report CR-CNS-2017-07513, and the licensee initiated a root cause evaluation.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On February 15, 2018, the inspectors presented the occupational radiation protection inspection results to Mr. J. Dent, Jr., Site Vice President and Chief Nuclear Officer, and other members of the licensee staff.
On March 12, 2018, the inspectors presented the results of the inspection of changes to the Cooper Nuclear Station emergency plan and emergency action levels to Mr. J. Stough, Manager, Emergency Preparedness, and other members of the licensee staff.
On April 16, 2018, the inspectors presented the quarterly resident inspector inspection results to Mr. J. Kalamaja, General Manager Plant Operations, and other members of the licensee staff.
DOCUMENTS REVIEWED
71111.01 - Adverse Weather Protection
Miscellaneous Documents
Title
Date
CNS Winter Weather Plan
January 10.
2018
List of Surveillance Procedures With Drop Dead Dates in the Next 5 Days
January 10,
2018
Procedures
Number
Title
Revision
2.1.11.1
Turbine Building Data
2
2.1.11.3
Radwaste and Augmented Radwaste Building Data
103
2.1.14
Seasonal Weather Preparations
5.1WEATHER
Operation During Weather Watches and Warnings
Condition Reports (CR-CNS-)
2018-00004
2018-00198
2018-00263
2018-00284
2018-00621
2018-00744
71111.04 - Equipment Alignment
Drawings
Number
Title
Revision
KSV46-5
Lube Oil Schematic
Miscellaneous Documents
Number
Title
Revision/Date
SWBP A Replacement Protected Equipment Program
Tracking Form
January 8,
2018
2031
Flow Diagram - Reactor Building - Closed Cooling Water
System, Sheet 2
N65
2040
Flow Diagram - Residual Heat Removal System Loop B,
Sheet 2
2077
Flow Diagram - Diesel Gen. Bldg. Service Water, Starting
Air, Fuel Oil, Sump System & Roof Drains
N78
Miscellaneous Documents
Number
Title
Revision/Date
VM-0245
Cooper Bessemer Diesel Generator Vendor Manual
Procedures
Number
Title
Revision
2.2A.DG.DIV1
Standby AC Power System (Diesel Generator) Component
Checklist (DIV 1)
2.2A.DG.DIV2
Standby AC Power System (Diesel Generator) Component
Checklist (DIV 2)
2.2A.REC.DIV2
Reactor Equipment Cooling Water System Component
Checklist (DIV 2)
2.2A.REC.DIV3
Reactor Equipment Cooling Water System Common
Divisional Component Checklist
2.2A.RHR.DIV2
Residual Heat Removal System Component Checklist
2.2B.DG.DIV2
Standby AC Power System (Diesel Generator) Instrument
Valve Checklist (DIV 2)
2.2B.REC.DIV2
Reactor Equipment Cooling Water System Instrument Valve
Checklist (DIV 2)
Condition Reports (CR-CNS-)
2018-01676
2018-01683
Work Orders
5145546
5167608
201413
71111.05 - Fire Protection
Drawings
CNS-FP-218
CNS-FP-236
CNS-FP-237
CNS-FP-245
Miscellaneous Documents
Number
Title
18-0006
Transient Combustible Permit
BCP-2017-0228
Barrier Control Permit
BCP-2018-0025
Barrier Control Permit
Procedures
Number
Title
Revision
0-BARRIER-
MAPS
Barrier Maps
0-BARRIER-
MISC
Miscellaneous Buildings
0-BARRIER-
REACTOR
Reactor Building
0-BARRIER-
TURBINE
Turbine Building
0.23
CNS Fire Protection Plan
2.3.1
General Alarm Procedure
15.FP.309
Fire Protection Manual Pull Station Functional Test
Condition Reports (CR-CNS-)
2018-01616
2018-01625
2018-01774
2018-01782
2018-01793
2018-01823
Work Orders
5167486
231480
71111.06 - Flood Protection Measures
Miscellaneous Documents
Number
Title
Revision
BCP-2017-0238
Barrier Control Permit
NEDC 09-102
Internal Flooding - HELB, MELB, and Feedwater Line
Break
Work Orders
5167308
5167485
71111.07 - Heat Sink Performance
Procedures
Number
Title
Revision
7.2.42.3
Heat Exchanger Tube Plugging
Procedures
Number
Title
Revision
13.17.2
Thermal Performance Test Procedure for Residual Heat
Removal Heat Exchangers
Condition Reports (CR-CNS-)
2018-00321
71111.11 - Licensed Operator Requalification Program and Licensed Operator
Performance
Miscellaneous Documents
Number
Title
Revision/Date
2018 1st Quarter Downpower; Just In Time Training
Initiation Form
January 14,
2018
DEP Performance Evaluation and Data Collection Form -
Scenario SKL052-52-17
January 23,
2018
Operations Pre-job Brief - Single Loop Operation Evolution
February 16,
2018
EPIP 5.7.1
Emergency Classification
EPIP 5.7.2
Emergency Director EPIP
SKL052-52-17
Licensed Operator Requalification Exam Scenario 17
January 3,
2018
Procedures
Number
Title
Revision
2.1.10
Station Power Changes
114
2.2.68.1
Reactor Recirculation System Operations
2.4RR
Reactor Recirculation Abnormal
Condition Reports (CR-CNS-)
2018-00892
2018-00896
2018-00898
2018-00914
2018-00919
2018-00921
71111.12 - Maintenance Effectiveness
Miscellaneous Documents
Number
Title
Revision
DG-PF01
Maintenance Rule Function DG-PF01 Performance Criteria
Basis Document
DGHV-PF04
Maintenance Rule Function DGHV-PF04 Performance
Criteria Basis Document
DGSA-PF01
Maintenance Rule Function DGSA-PF01 Performance
Criteria Basis Document
Procedures
Number
Title
Revision
3-EN-DC-204
Maintenance Rule Scope and Basis
3C1
3-EN-DC-206
Maintenance Rule (a)(1) Process
3C2
7.3.1.19
GE IJCV-51A/IFCV-51AD Overcurrent Relay Testing and
Maintenance
Condition Reports (CR-CNS-)
2000-02070
2015-06608
2016-00141
2016-03335
2017-00551
2017-01168
2017-02533
2017-02538
2017-04451
2017-05821
2017-06408
2018-00685
2018-00832
Work Orders
5115005
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Miscellaneous Documents
Number
Title
Revision/Date
DG2 LCO Protected Equipment Program Tracking Form
March 22,
2018
Div 1 DG Maintenance Window Protected Equipment
Program Tracking Form
February 6,
2018
Remain in Service List for Div 1 DG Work Window
SW-MOV-651 Maintenance Protected Equipment Program
Tracking Form
January 20,
2018
Miscellaneous Documents
Number
Title
Revision/Date
SWBP A Replacement Protected Equipment Program
Tracking Form
January 8,
2018
SWBP D Maintenance Window Protected Equipment
Program Tracking Form
January 16,
2018
11-198
Cooper Nuclear Station Service Water System Analysis
Procedures
Number
Title
Revision
0-CNS-WM-104
On-Line Schedule Risk Assessment
0-CNS-WM-
104A
On-Line Fire Risk Management Actions
0-PROTECT-
EQP
Protected Equipment Program
2.1.1
Startup Procedure
190
2.1.10
Station Power Changes
114
2.1.4.3
Power Reduction to <25/30%
2.2.68.1
Reactor Recirculation System Operations
2.2.71
Service Water System
2
2.3_A-4
Annunciator Response Procedure - Panel A-4
7.0.1.7
Troubleshooting Plant Equipment
Condition Reports (CR-CNS-)
2018-00138
2018-00291
2018-00292
2018-00328
2018-00341
2018-00342
2018-00352
2018-00371
2018-00375
2018-00376
2018-00377
2018-00461
2018-00541
2018-00657
2018-00658
2018-01597
2018-01649
Work Orders
5145546
5167094
5167469
5167606
5175025
201054
201413
203083
213083
231297
71111.15 - Operability Determinations and Functionality Assessments
Miscellaneous Documents
Number
Title
Revision
CNS Inservice Testing Basis Document
Failure Modes and Effects Analysis - SW-TE-387B
Indicated Flow with SW-MOV-651MV Closed
2036
Reactor Building Service Water System, Sheet 1
A3
2036
Control Building Service Water System, Sheet 4
PAD 121987
Process Applicability Determination for Isolation of REC
Division 2 SW Flow Path
Procedures
Number
Title
Revision
6.2SW.101
Service Water Surveillance Operation, Div 2 (IST)
Condition Reports (CR-CNS-)
2017-03717
2017-05742
2017-05797
2017-05819
2017-06869
2018-00007
2018-00122
2018-00142
2018-00182
2018-00299
2018-00342
2018-00354
2018-00362
2018-00459
2018-00461
2018-00538
2018-01621
2018-01644
2018-01651
Work Orders
206535
71111.18 - Plant Modifications
Miscellaneous Documents
Number
Title
Revision/Date
2036
Reactor Building Service Water System, Sheet 1
A3
2036
Control Building Service Water System, Sheet 4
EE 2013-04
RHR SWBP FCU 50.59 Inadequate for USAR Change LCR
93-10
LCR 93-0010
Specify a Summer Design Temperature of 131°F for the
RHR SWBP Room
February 5,
1993
Miscellaneous Documents
Number
Title
Revision/Date
NEDC 92-063
Maximum SWBP Room Temperatures w/ No Cooling From
Control Bldg HVAC
NEDC 92-064
Transient Temperature Rise in SWBP Room After Loss of
Cooling
3C2
PAD 121987
Process Applicability Determination for Isolation of REC
Division 2 SW Flow Path
TCC-5231919
Temporary Configuration Change - Replacement of
SW-V-126 With Blind Flange Spool Piece
UCR 98-019
USAR Change Request: SWBP Fan Coil Unit Description
Removal
April 28, 1998
Procedures
Number
Title
Revision
2.2.71
Service Water System
2
2.3_R-1
Panel R - Annunciator R-1
17, 18
7.3.50.4
SW-650MV and SW-651MV Flow Adjustment
Condition Reports (CR-CNS-)
2017-06120
2017-06196
2017-06241
2017-07601
2018-00342
2018-00362
2018-00461
Work Orders
231297
231480
232377
71111.19 - Post-Maintenance Testing
Drawings
Number
Title
Revision
454223426
Emergency Diesel Generator Composite Control Air
Schematic
Miscellaneous Documents
Number
Title
Revision
11445276
Notification
IST Reference/Acceptance Limits Data File
246
Procedures
Number
Title
Revision
2.2.20.1
Diesel Generator Operations
69, 70
6.1DG.101
Diesel Generator 31 Day Operability Test (IST)(DIV 1)
6.1HV.602
Air Flow Test of Fan Coil Unit HV-DG-1C (DIV 1)
6.1SWBP.101
RHR Service Water Booster Pump Flow Test and Valve
Operability Test (DIV 1)
6.2HV.603
Air Flow Test of Fan Coil Unit for FC-R-1H (Div 2)
6.2SW.101
Service Water Surveillance Operation Div 2 (IST)
6.SW.102
Service Water System Post-LOCA Flow Verification
7.0.5
CNS Post-Maintenance Testing
7.0.8.1
System Leakage Testing
7.3.50.4
SW-650MV and SW-651MV Flow Adjustment
14.17.1
DG-1 Annual Calibration
14.28.1
Service Water System Instrument Calibration
Condition Reports (CR-CNS-)
2016-07426
2018-00388
2018-00342
2018-00425
2018-00461
2018-00521
2018-00711
2018-00715
2018-00751
2018-00765
2018-01714
2018-01715
Work Orders
4832440
5145546
5145577
5167078
5167385
5167606
5167617
5169763
5169764
5169985
5184976
5188894
201054
201413
231297
231480
71111.20 - Refueling and Other Outage Activities
Procedures
Number
Title
Revision
2.1.4
Normal Shutdown
157
6.RCS.601
Technical Specification Monitoring of RCS
Heatup/Cooldown Rate
71111.22 - Surveillance Testing
Miscellaneous Documents
Number
Title
Revision/Date
List of Drywell Possible Leak Sources
January 23,
2018
Summary of Primary Containment Sample Results for
Current Fuel Cycle
February 2,
2018
EC 18-003
6.LOG.601 Revision to Address Effects of Voiding on
Drywell Floor Drain Sump Flow Indication
0, 1
Procedures
Number
Title
Revision
6.DWLD.301
Drywell Floor Drain Sump Flow Measuring System
Functional Test
6.DWLD.302
Drywell Floor Drain Sump 1F Flow Loop Channel
Calibration
6.LOG.601
Daily Surveillance Log - Modes 1, 2, and 3
130, 131, 132
6.RCIC.102
6.RR.601B
RRMG B Positioner Maintenance and Setting Electrical and
Mechanical Stops
6.1DG.101
Diesel Generator 31 Day Operability Test (IST)(DIV 1)
15.SUMP.101
Sump Pump Operability Test
Drywell Leakage
Condition Reports (CR-CNS-)
2012-07093
2017-06119
2017-06820
2018-00123
2018-00127
2018-00310
2018-00336
2018-00340
2018-00436
2018-00905
2018-00907
Work Orders
5047898
5099572
5101207
5103351
5114307
5115900
23387
5167175
5177984
5190520
231292
71114.04 - Emergency Action Level and Emergency Plan Changes
Miscellaneous Documents
Number
Title
Revision
Cooper Nuclear Station Emergency Plan
EPIP 5.7.1
Emergency Classification
71114.06 - Drill Evaluation
Miscellaneous Documents
Number
Title
Revision/Date
DEP Performance Evaluation and Data Collection Form -
Scenario SKL052-52-17
January 23,
2018
EPIP 5.7.1
Emergency Classification
EPIP 5.7.2
Emergency Director EPIP
SKL052-52-17
Licensed Operator Requalification Exam Scenario 17
January 3,
2018
71124.02 - Occupational ALARA Planning and Controls
ALARA Committee Meeting Minutes
Meeting
Title
Date
February
Meeting Minutes
February
2017
August
Meeting Minutes
August 2017
October
Meeting Minutes
October 2017
December
Meeting Minutes
December
2017
ALARA Planning, In-Progress Reviews, and Post-Job Reviews
Number
Title
Date
2016-01
RE29 CRDM Replacements
November 5,
2016
2016-03
RWCU Pump B Replace Power Frame
June 8, 2016
2016-05
RE-29 Refuel Floor Activities
November 5,
2016
2016-12
December
14, 2016
ALARA Planning, In-Progress Reviews, and Post-Job Reviews
Number
Title
Date
2016-23
RR-A Motor, Impeller and Seal
November 6,
2016
2017-01
Spent Fuel Pool Clean-Up Project (Online)
December
11, 2017
Audits and Self-Assessments
Number
Title
Date
LO-2017-0204
Focused Self-Assessment:
Occupational ALARA Planning and Controls
December 1,
2017
Miscellaneous Documents
Title
5-Year CRE Reduction Plan (2018-2022)
RE29 Radiological Post Outage Report
2017 Cooper Nuclear Station ALARA Program
Procedures
Number
Title
Revision
9.ALARA.4
Radiation Work Permits
9.ALARA.8
ALARA Document Control
ALARA Program
9.EN-RP-110-03 Collective Radiation Exposure (CRE) Reduction Guidelines
9.EN-RP-110-04 Radiation Protection Risk Assessment Process
9.EN-RP-110-05 ALARA Planning and Controls
9.EN-RP-110-06 Outage Dose Estimating and Tracking
Radiation Work Permits
Number
Title
Revision
2016-014
Refuel Floor Activities
2016-055
RWCU-P-B Replacement and RWCU-CV11 Inspection
2016-060
Refuel Floor General SWP Work
2016-406
CRDMs Support - Support Work - RWP (NO ENTRY
ALLOWED INTO AN AREA POSTED SWP)
Radiation Work Permits
Number
Title
Revision
2016-506
Under vessel CRDMs Change outs Also Keyway Worker
and RP Under vessel Coverage
2016-523
RR-A Motor and Impeller Replacement in RE29 - SWP
2017-107
2017 SFP Cleanup
Condition Reports (CR-CNS-)
2016-06415
2016-06567
2016-07197
2016-08576
2017-02319
2017-04201
2017-04896
2017-04899
2017-05538
2017-06603
71124.04 - Occupational Dose Assessment
Audits and Self-Assessments
Number
Title
Date
Radiation Protection Program Annual Report
2016
16-05
QA Audit of Radiological Controls
August 10,
2016
LO-2017-0204
Focused Self-Assessment:
Occupational Dose Assessment
December 1,
2017
Miscellaneous Documents
Title
Date
2016 DAW Part 61 Analysis
March 29,
2017
100555-0 National Voluntary Laboratory Accreditation Program (NVLAP)
Certificate for Mirion Technologies
July 1, 2017
Internal Dose Assessment Prospectus
2017
Internal Dose Assessment Prospectus
2018
Multiplication Factor for the Merlin Gerin DMC 2000S (White Paper)
March 22,
2012
Procedures
Number
Title
Revision
9.ALARA.1
Personnel Dosimetry and Occupational Radiation Exposure 47
9.ALARA.13
Radiation Worker and Tour Group Dosimetry Management
Procedures
Number
Title
Revision
Radiological Control
Personnel Contamination
9.EN-RP-110-05 ALARA Planning and Controls
Alpha Monitoring
Dose Assessment
Prenatal Monitoring
Dosimeter of Legal Record Quality Assurance
Whole Body Counting and In-Vitro Bioassay
Area Monitoring Program
Self-Reading Dosimeters
9.RADOP.1
Radiation Protection at CNS
9.RADOP.5
Airborne Radioactivity Sampling
Condition Reports (CR-CNS-)
2016-01718
2016-04881
2016-07077
2017-04996
2017-05538
71151 - Performance Indicator Verification
Procedures
Number
Title
Revision
Performance Indicator Process
5C2
71152 - Problem Identification and Resolution
Miscellaneous Documents
Number
Title
Revision/Date
3059
EE-PNL-DG1 125VDC Load & Fuse Schedule, Sheet 11
3059
EE-PNL-DG2 125VDC Load & Fuse Schedule, Sheet 12
EE 2018-001
Characterization of Potential Risk of EDG Indicating Light
Failure
0, 1
G5-262-743
Emergency Diesel Generator #1 Electrical Schematic
Sheet 1
Miscellaneous Documents
Number
Title
Revision/Date
G5-262-743
Emergency Diesel Generator #2 Electrical Schematic
Sheet 1
NPP-61852
Failure Analysis of a Lamp Assembly
November
27, 2017
PAD 121981
Process Applicability Determination - Caution Order:
DG-1-DG-SW-DG2(43CM) Green Ind
PAD 121982
Process Applicability Determination - Caution Order:
DG-1-DG #1 Bulb Control
Condition Reports (CR-CNS-)
2017-01168
2017-05434
2017-05456
2017-06219
2017-07078
2017-07513
2018-00124
2018-00125
2018-00685
2018-00832
2018-01281
Work Orders
26885
71153 - Follow-up of Events and Notices of Enforcement Discretion
Procedures
Number
Title
Revision
2.0.5
Reports to NRC Operations Center
NRC Request for Information
System: Emergency Diesel Generators, Divisions 1 and 2
CD Date Requested by: January 2, 2018
Date Range of Document Request: December 31, 2015 - Current
Please provide the following documents:
1. Copies of all root and apparent cause evaluations performed on this system.
2. Summary list of all condition reports written on this system, sorted by CR classification
3. List of all surveillances performed on this system, sortable by component if possible.
4. Provide copies of the three most recently completed quarterly surveillances for both
divisions
5. List of all corrective maintenance work orders, with description of work, performed on this
system
6. Provide a list of control room deficiencies associated with this system
7. Copies of ODMIs, OWA/OWBs, prompt operability evaluations, and standing orders
associated with this system
8. Summarized list of all Maintenance Rule equipment issues evaluated for the system,
(including their conclusions), copies of each MRule evaluation for the system, and the
MRule Basis Document(s) for the system
9. List of all work orders, with description of work, planned for this system within the next year
10. Provide a list and description of overdue PMs, deferred PMs, and PM change requests for
this system
11. Provide copies of maintenance rule functional failure assessmentsregardless of the
resultperformed on these systems. Include CR number for each item on the list.
2. System design calculations for DG loading capabilities
13. Provide fire impairments associated with this system
14. Provide copies of any QA audits or self-assessments associated with this system
15. Copies of vendor manuals, drawings (P&IDs), and system training manuals
16. System health reports and system engineering logs for this system
17. List and description of temporary modifications; completed ECs (December 31, 2015 -
Current); and planned ECs (within the next year) associated with this system
18. Schedule of activities (Fragnets) for the planned AOT for the Division 1 and 2 DGs
scheduled for the work weeks of 1806 and 1812.
The following items are requested for the
Occupational Radiation Safety Inspection
at Cooper Nuclear Station
(February 12-16, 2018)
Integrated Report 2018001
Inspection areas are listed in the attachments below.
Please provide the requested information on or before January 25, 2018.
Please submit this information using the same lettering system as below. For example, all
contacts and phone numbers for Inspection Procedure 71124.01 should be in a file/folder titled
1-A, applicable organization charts in file/folder 1-B, etc.
If information is placed on ims.certrec.com, please ensure the inspection exit date entered is at
least 30 days later than the onsite inspection dates, so the inspectors will have access to the
information while writing the report.
In addition to the corrective action document lists provided for each inspection procedure listed
below, please provide updated lists of corrective action documents at the entrance meeting.
The dates for these lists should range from the end dates of the original lists to the day of the
entrance meeting.
If more than one inspection procedure is to be conducted and the information requests appear
to be redundant, there is no need to provide duplicate copies. Enter a note explaining in which
file the information can be found.
If you have any questions or comments, please contact John ODonnell at (817) 200-1441 or
john.odonnell@nrc.gov. The other inspector will be Shawn Money.
PAPERWORK REDUCTION ACT STATEMENT
This letter does not contain new or amended information collection requirements subject
to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information
collection requirements were approved by the Office of Management and Budget,
control number 3150-0011.
2.
Occupational ALARA Planning and Controls (71124.02)
Date of Last Inspection:
October 3, 2016
A.
List of contacts and telephone numbers for ALARA program personnel
B.
Applicable organization charts
C.
Copies of audits, self-assessments, and LERs, written since date of last inspection,
focusing on ALARA
D.
Procedure index for ALARA Program
E.
Please provide specific procedures related to the following areas noted below.
Additional Specific Procedures may be requested by number after the inspector reviews
the procedure indexes.
1. ALARA Program
2. ALARA Committee
3. Radiation Work Permit Preparation
F.
A summary list of corrective action documents (including corporate and sub-tiered
systems) written since date of last inspection, related to the ALARA program. In addition
to ALARA, the summary should also address Radiation Work Permit violations,
Electronic Dosimeter Alarms, and RWP Dose Estimates
NOTE: The lists should indicate the significance level of each issue and the search
criteria used. Please provide in document formats which are searchable so that
the inspector can perform word searches.
G.
List of work activities greater than 1 rem, since date of last inspection,
Include original dose estimate and actual dose.
H.
Site dose totals and 3-year rolling averages for the past 3 years (based on dose of
record)
I.
Outline of source term reduction strategy
J.
If available, provide a copy of the ALARA outage report for the most recently completed
outages for each unit
K.
Please provide your most recent Annual ALARA Report.
4. Occupational Dose Assessment (Inspection Procedure 71124.04)
Date of Last Inspection:
March 23, 2016
A.
List of contacts and telephone numbers for the following areas:
1. Dose Assessment personnel
B.
Applicable organization charts
C.
Audits, self-assessments, vendor or NUPIC audits of contractor support, and LERs
written since date of last inspection, related to:
1. Occupational Dose Assessment
D.
Procedure indexes for the following areas:
1. Occupational Dose Assessment
E.
Please provide specific procedures related to the following areas noted below.
Additional Specific Procedures will be requested by number after the inspector reviews
the procedure indexes.
1. Radiation Protection Program
2. Radiation Protection Conduct of Operations
3. Personnel Dosimetry Program
4. Radiological Posting and Warning Devices
5. Air Sample Analysis
6. Performance of High Exposure Work
7. Declared Pregnant Worker
8. Bioassay Program
F.
List of corrective action documents (including corporate and sub-tiered systems) written
since date of last inspection, associated with:
1. National Voluntary Laboratory Accreditation Program (NVLAP)
2. Dosimetry (TLD/OSL, etc.) problems
3. Electronic alarming dosimeters
4. Bioassays or internally deposited radionuclides or internal dose
5. Neutron dose
NOTE: The lists should indicate the significance level of each issue and the search
criteria used. Please provide in document formats which are searchable so that
the inspector can perform word searches.
G.
List of positive whole body counts since date of last inspection, names redacted if
desired
H.
Part 61 analyses/scaling factors
I.
The most recent NVLAP accreditation report or, if dosimetry is provided by a vendor, the
vendors most recent results
SUNSI Review
By: CHY/rdr
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available
Keyword:
OFFICE
ASRI:DRP/C
RI:DRP/C
BC:DRS/EB1
BC:DRS/EB2
BC:DRS/OB
BC:DRS/PSB2
NAME
RKumana
MStafford
TFarnholtz
JDrake
VGaddy
HGepford
SIGNATURE
/RA/
/RA/
/RA/
/RA/
/RA/
/RA/
DATE
4/23/18
4/23/18
04/23/2018
4/23/2018
4/24/18
4/23/18
OFFICE
TL:DRS/IPAT
SPE:DRP/C
BC:DRP/C
NAME
GGeorge
CYoung
JKozal
SIGNATURE
/RA/
/RA/
/RA/
DATE
4/24/2018
4/27/2018
5/08/2018
May 8, 2018
Mr. John Dent, Jr.
Vice President-Nuclear and CNO
Nebraska Public Power District
Cooper Nuclear Station
2676 648A Avenue
P.O. Box 98
Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - NRC INTEGRATED INSPECTION REPORT
Dear Mr. Dent:
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection
at your Cooper Nuclear Station. On April 16, 2018, the NRC inspectors discussed the results of
this inspection with Mr.
- J. Kalamaja, General Manager Plant Operations, and other members of
your staff. The results of this inspection are documented in the enclosed report.
No NRC-identified or self-revealed findings were identified during this inspection.
However, inspectors documented a licensee-identified violation, which was determined to be of
very low safety significance, in this report. The NRC is treating this violation as a non-cited
violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.
J. Dent Jr.
This letter, its enclosure, and your response (if any) will be made available for public inspection
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for
Withholding.
Sincerely,
/RA/
Jason Kozal, Chief
Project Branch C
Division of Reactor Projects
Docket No. 50-298
License No. DPR-46
Enclosure:
Inspection Report 05000298/2018001
w/ Attachments:
1. Documents Reviewed
2. NRC Request for Information
3. Occupational Radiation Safety Inspection
Request for Information
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number:
05000298
License Number:
Report Number:
Enterprise Identifier: I-2018-001-0003
Licensee:
Nebraska Public Power District
Facility:
Cooper Nuclear Station
Location:
2676 648A Ave
Brownville, NE
Inspection Dates:
January 1, 2018 to March 31, 2018
Inspectors:
- P. Voss, Senior Resident Inspector
- R. Kumana, Acting Senior Resident Inspector
- M. Stafford, Resident Inspector
- P. Elkmann, Senior Emergency Preparedness Inspector
- S. Money, Health Physicist
- J. ODonnell, CHP, Health Physicist
Approved By:
- J. Kozal, Branch Chief
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees
performance by conducting an integrated inspection at Cooper Nuclear Station, in accordance
with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for
overseeing the safe operation of commercial nuclear power reactors. Refer to
https://www.nrc.gov/reactors/operating/oversight.html for more information. A licensee-
identified, non-cited violation is documented in report Section 71152.
No findings were identified.
PLANT STATUS
Cooper Nuclear Station began the inspection period at rated thermal power. On
February 16, 2018, the licensee reduced power to 36 percent in order to enter single loop
operation to perform maintenance on reactor recirculation motor generator B, repair condenser
leaks, perform maintenance on control rod drives, and tune a reactor recirculation system motor
generator set. The licensee restored power to 100 percent on February 18, 2018. On
March 11, 2018, the licensee performed a normal shutdown to repair a reactor coolant leak
inside the drywell. The licensee restarted the reactor on March 16, 2018, and resumed full
power operation on March 19, 2018. The licensee maintained full power for the remainder of
the reporting period, except for minor reductions in power to support scheduled surveillances
and rod pattern adjustments.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in
effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with
their attached revision histories are located on the public website at http://www.nrc.gov/reading-
rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared
complete when the IP requirements most appropriate to the inspection activity were met
consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection
Program - Operations Phase. The inspectors performed plant status activities described in
IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem
Identification and Resolution. The inspectors reviewed selected procedures and records,
observed activities, and interviewed personnel to assess licensee performance and compliance
with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather (1 Sample)
The inspectors evaluated readiness for seasonal extreme weather conditions prior to the
onset of seasonal cold temperatures.
Impending Severe Weather (1 Sample)
The inspectors evaluated readiness for impending adverse weather conditions for a winter
weather advisory on January 10, 2018.
71111.04 - Equipment Alignment
Partial Walkdown (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following
systems/trains:
(1) Division 2 residual heat removal during service water booster pump A replacement on
January 12, 2018
(2) Division 2 reactor equipment cooling during Division 1 reactor equipment cooling
maintenance window on January 31, 2018
(3) Emergency diesel generator 2 lube oil during emergency diesel generator 1 work
window on February 7, 2017
(4) Emergency diesel generator 1 starting air during emergency diesel generator 2 work
window on March 22, 2018
71111.05AQ - Fire Protection Annual/Quarterly
Quarterly Inspection (4 Samples)
The inspectors evaluated fire protection program implementation in the following selected
areas:
(1) Reactor building 931 foot elevation, Fire Area RB-M, Zones 3C and 3D on
January 31, 2018
(2) Emergency diesel generator 1, Fire Area DG-A, Zone 14A on February 26, 2018
(3) Condensate pump area, turbine building 882 foot elevation, Fire Area TB-A, Zone 11J
on March 20, 2018
(4) Emergency diesel generator 2, Fire Area DG-B, Zone 14B on March 26, 2018
71111.06 - Flood Protection Measures
Internal Flooding (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the reactor building
931 foot elevation, reactor equipment cooling heat exchanger area on February 22, 2018.
71111.07 - Heat Sink Performance
Heat Sink (1 Sample)
The inspectors evaluated a residual heat removal heat exchanger thermal performance test
on January 17, 2018.
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance
Operator Requalification (1 Sample)
The inspectors observed and evaluated a licensed operator requalification scenario in the
simulator on January 23, 2018.
Operator Performance (1 Sample)
The inspectors observed and evaluated the quarterly downpower, including entry into single
loop operations, power reduction to 45 percent, and planned trip of reactor recirculation
motor generator set B and the associated pre-job briefs on February 17, 2018.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness (1 Sample)
The inspectors evaluated the effectiveness of routine maintenance activities associated
with the following equipment and/or safety significant functions:
(1) Emergency diesel generator 2 system a(1) evaluation due to exceeding performance
criteria on March 9, 2018
71111.13 - Maintenance Risk Assessments and Emergent Work Control (7 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent
work activities:
(1) Service water booster pump A replacement on January 9, 2018
(2) Service water booster pump D maintenance window on January 17, 2018
(3) Emergent service water valve maintenance due to reactor equipment cooling heat
exchanger B leakage on January 29, 2018
(4) Emergency diesel generator 1 work window on February 6, 2018
(5) Reactor recirculation motor generator set maintenance and single loop operation on
February 17, 2018
(6) Emergent steam leak repair affecting high pressure coolant injection on March 8, 2018
(7) Emergency diesel generator 2 work window on March 23, 2018
71111.15 - Operability Determinations and Functionality Assessments (4 Samples)
The inspectors evaluated the following operability determinations and functionality
assessments:
(1) Jet pump 12 differential pressure reading step change on January 22, 2018
(2) Reactor equipment cooling heat exchanger outlet valve SW-MO-651 indications of
potential leak path on January 22, 2018
(3) Scram discharge volume shielding evaluation on January 25, 2018
(4) Emergency diesel generator 2 field flash resistor insulation issue and extent of condition
for emergency diesel generator 1 on March 23, 2018
71111.18 - Plant Modifications (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
(1) Reactor equipment cooling heat exchanger B, SW-V-126 temporary flange on
February 5, 2018
71111.19 - Post Maintenance Testing (5 Samples)
The inspectors evaluated the following post maintenance tests:
(1) Service water booster pump A replacement on January 16, 2018
(2) Post maintenance test for emergency diesel generator 1 system maintenance on
February 20, 2018
(3) South west residual heat removal quad fan coil unit maintenance on February 23, 2018
(4) Unplanned service water valve maintenance due to reactor equipment cooling heat
exchanger B leakage on February 26, 2018
(5) Post maintenance test for emergency diesel generator 2 system maintenance on
March 23, 2018
71111.20 - Refueling and Other Outage Activities (1 Sample)
The inspectors evaluated forced outage activities due to reactor coolant system leakage
from March 12, 2018, to March 16, 2018.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Routine (2 Samples)
(1) Emergency diesel generator 1, 31-day operability test on January 8, 2018
(2) Reactor recirculation motor generator set B surveillance testing on February 17, 2018
In-service (1 Sample)
(1) Reactor core isolation cooling quarterly in-service surveillance test on March 29, 2018
Reactor Coolant System Leak Detection (1 Sample)
(1) Drywell unidentified leakage integrator functional test and calibration on
February 20, 2018
71114.04 - Emergency Action Level and Emergency Plan Changes (2 Samples)
The inspector evaluated two submitted Emergency Action Level and Emergency Plan
changes in-office on January 30, 2018, and March 12, 2018. This evaluation does not
constitute NRC approval.
71114.06 - Drill Evaluation
Drill/Training Evolution (1 Sample)
The inspectors evaluated the licensed operator training scenario in the simulator control
room on January 23, 2018.
RADIATION SAFETY
71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls
Radiological Work Planning (1 Sample)
The inspectors evaluated the licensees radiological work planning by reviewing the
following activities:
(1) 2016-01, refueling outage 29 control rod drive mechanism replacements
(2) 2016-03, reactor water cleanup pump B replace power frame
(3) 2016-05, RE-29 refuel floor activities
(4) 2016-12, RE-29, in-service inspection and flow accelerated corrosion exams
(5) 2016-23, reactor recirculation pump A motor, impeller, and seal
(6) 2017-01, spent fuel pool clean-up project (Online)
Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)
The inspectors evaluated dose estimates and exposure tracking.
71124.04 - Occupational Dose Assessment
Source Term Characterization (1 Sample)
The inspectors evaluated the licensees source term characterization.
External Dosimetry (1 Sample)
The inspectors evaluated the licensees external dosimetry program.
Internal Dosimetry (1 Sample)
The inspectors evaluated the licensees internal dosimetry program.
Special Dosimetric Situations (1 Sample)
The inspectors evaluated the licensees performance for special dosimetric situations.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below. (2 Samples)
(1)
IE01: Unplanned Scrams per 7000 Critical Hours Sample (January 1,2017, through
December 31, 2017)
(2)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (January 1, 2017,
through December 31, 2017)
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program
related to the following issues:
(1) Both emergency diesel generators declared inoperable due to light bulb socket
deficiencies
71153 - Follow-up of Events and Notices of Enforcement Discretion
Events (1 Sample)
The inspectors evaluated the failure of the primary alert and notification system and the
licensees response on March 16, 2018.
INSPECTION RESULTS
Licensee Identified Non-Cited Violation
This violation of very low safety significance was identified by the licensee and has been
entered into the licensee corrective action program and is being treated as a non-cited
violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Title 10 CFR Part 50, Appendix B, Criterion III, Design Control, requires, in part,
that for those systems, structures, and components to which this appendix applies, Design
control measures shall provide for verifying or checking the adequacy of design.
Contrary to the above, between September 2003, and December 19, 2017, the licensee failed
to verify or check the adequacy of design of quality-related components associated with the
Division 1 and 2 emergency diesel generator 125 Vdc control power circuits. Specifically,
in 2003, the licensee modified the design of the control power circuit through Part
Evaluation (PE) 4222806 and replaced 24 original light bulb lamp assemblies with a different
style of light bulb and a carbon film dropping resistor (vs. the original wire-wound design).
This change created an unrecognized vulnerability that left the affected portions of the circuit
with dropping resistors that provided insufficient protection from shorting due to indication light
bulb failures. As a result, on December 19, 2017, the licensee declared both emergency
diesel generators inoperable due to the design vulnerability.
Significance/Severity Level: The finding created a design vulnerability in the emergency
diesel generator control power circuits, and resulted in the Division 1 and 2 emergency diesel
generators being declared inoperable at the time of discovery. Although the emergency
diesel generators were declared inoperable, subsequent licensee analysis determined that
the system retained its function, and maintained a reasonable expectation of operability while
the design deficiencies existed. Accordingly, the inspectors assessed the significance of this
finding in accordance with Inspection Manual Chapter 0609, Appendix A, The Significance
Determination Process (SDP) for Findings at Power, dated June 19, 2012, and determined
this finding was of very low safety significance (Green) because it was a deficiency affecting
the design or qualification of a mitigating structure, system, or component (SSC), but the SSC
maintained its operability.
Corrective Action Reference(s): Immediate corrective actions included compensatory
measures to remove light bulbs from the vulnerable lamp assemblies in order to eliminate the
shorting hazard. This issue was entered into the licensees corrective action program as
Condition Report CR-CNS-2017-07513, and the licensee initiated a root cause evaluation.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On February 15, 2018, the inspectors presented the occupational radiation protection inspection
results to Mr.
- J. Dent, Jr., Site Vice President and Chief Nuclear Officer, and other members of
the licensee staff.
On March 12, 2018, the inspectors presented the results of the inspection of changes to the
Cooper Nuclear Station emergency plan and emergency action levels to Mr.
Manager, Emergency Preparedness, and other members of the licensee staff.
On April 16, 2018, the inspectors presented the quarterly resident inspector inspection results to
Mr.
- J. Kalamaja, General Manager Plant Operations, and other members of the licensee staff.
DOCUMENTS REVIEWED
71111.01 - Adverse Weather Protection
Miscellaneous Documents
Title
Date
CNS Winter Weather Plan
January 10.
2018
List of Surveillance Procedures With Drop Dead Dates in the Next 5 Days
January 10,
2018
Procedures
Number
Title
Revision
2.1.11.1
Turbine Building Data
2
2.1.11.3
Radwaste and Augmented Radwaste Building Data
103
2.1.14
Seasonal Weather Preparations
5.1WEATHER
Operation During Weather Watches and Warnings
Condition Reports (CR-CNS-)
2018-00004
2018-00198
2018-00263
2018-00284
2018-00621
2018-00744
71111.04 - Equipment Alignment
Drawings
Number
Title
Revision
KSV46-5
Lube Oil Schematic
Miscellaneous Documents
Number
Title
Revision/Date
SWBP A Replacement Protected Equipment Program
Tracking Form
January 8,
2018
2031
Flow Diagram - Reactor Building - Closed Cooling Water
System, Sheet 2
N65
2040
Flow Diagram - Residual Heat Removal System Loop B,
Sheet 2
2077
Flow Diagram - Diesel Gen. Bldg. Service Water, Starting
Air, Fuel Oil, Sump System & Roof Drains
N78
Miscellaneous Documents
Number
Title
Revision/Date
VM-0245
Cooper Bessemer Diesel Generator Vendor Manual
Procedures
Number
Title
Revision
2.2A.DG.DIV1
Standby AC Power System (Diesel Generator) Component
Checklist (DIV 1)
2.2A.DG.DIV2
Standby AC Power System (Diesel Generator) Component
Checklist (DIV 2)
2.2A.REC.DIV2
Reactor Equipment Cooling Water System Component
Checklist (DIV 2)
2.2A.REC.DIV3
Reactor Equipment Cooling Water System Common
Divisional Component Checklist
2.2A.RHR.DIV2
Residual Heat Removal System Component Checklist
2.2B.DG.DIV2
Standby AC Power System (Diesel Generator) Instrument
Valve Checklist (DIV 2)
2.2B.REC.DIV2
Reactor Equipment Cooling Water System Instrument Valve
Checklist (DIV 2)
Condition Reports (CR-CNS-)
2018-01676
2018-01683
Work Orders
5145546
5167608
201413
71111.05 - Fire Protection
Drawings
CNS-FP-218
CNS-FP-236
CNS-FP-237
CNS-FP-245
Miscellaneous Documents
Number
Title
18-0006
Transient Combustible Permit
BCP-2017-0228
Barrier Control Permit
BCP-2018-0025
Barrier Control Permit
Procedures
Number
Title
Revision
0-BARRIER-
MAPS
Barrier Maps
0-BARRIER-
MISC
Miscellaneous Buildings
0-BARRIER-
REACTOR
Reactor Building
0-BARRIER-
TURBINE
Turbine Building
0.23
CNS Fire Protection Plan
2.3.1
General Alarm Procedure
15.FP.309
Fire Protection Manual Pull Station Functional Test
Condition Reports (CR-CNS-)
2018-01616
2018-01625
2018-01774
2018-01782
2018-01793
2018-01823
Work Orders
5167486
231480
71111.06 - Flood Protection Measures
Miscellaneous Documents
Number
Title
Revision
BCP-2017-0238
Barrier Control Permit
NEDC 09-102
Internal Flooding - HELB, MELB, and Feedwater Line
Break
Work Orders
5167308
5167485
71111.07 - Heat Sink Performance
Procedures
Number
Title
Revision
7.2.42.3
Heat Exchanger Tube Plugging
Procedures
Number
Title
Revision
13.17.2
Thermal Performance Test Procedure for Residual Heat
Removal Heat Exchangers
Condition Reports (CR-CNS-)
2018-00321
71111.11 - Licensed Operator Requalification Program and Licensed Operator
Performance
Miscellaneous Documents
Number
Title
Revision/Date
2018 1st Quarter Downpower; Just In Time Training
Initiation Form
January 14,
2018
DEP Performance Evaluation and Data Collection Form -
Scenario SKL052-52-17
January 23,
2018
Operations Pre-job Brief - Single Loop Operation Evolution
February 16,
2018
EPIP 5.7.1
Emergency Classification
EPIP 5.7.2
Emergency Director EPIP
SKL052-52-17
Licensed Operator Requalification Exam Scenario 17
January 3,
2018
Procedures
Number
Title
Revision
2.1.10
Station Power Changes
114
2.2.68.1
Reactor Recirculation System Operations
2.4RR
Reactor Recirculation Abnormal
Condition Reports (CR-CNS-)
2018-00892
2018-00896
2018-00898
2018-00914
2018-00919
2018-00921
71111.12 - Maintenance Effectiveness
Miscellaneous Documents
Number
Title
Revision
DG-PF01
Maintenance Rule Function DG-PF01 Performance Criteria
Basis Document
DGHV-PF04
Maintenance Rule Function DGHV-PF04 Performance
Criteria Basis Document
DGSA-PF01
Maintenance Rule Function DGSA-PF01 Performance
Criteria Basis Document
Procedures
Number
Title
Revision
3-EN-DC-204
Maintenance Rule Scope and Basis
3C1
3-EN-DC-206
Maintenance Rule (a)(1) Process
3C2
7.3.1.19
GE IJCV-51A/IFCV-51AD Overcurrent Relay Testing and
Maintenance
Condition Reports (CR-CNS-)
2000-02070
2015-06608
2016-00141
2016-03335
2017-00551
2017-01168
2017-02533
2017-02538
2017-04451
2017-05821
2017-06408
2018-00685
2018-00832
Work Orders
5115005
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Miscellaneous Documents
Number
Title
Revision/Date
DG2 LCO Protected Equipment Program Tracking Form
March 22,
2018
Div 1 DG Maintenance Window Protected Equipment
Program Tracking Form
February 6,
2018
Remain in Service List for Div 1 DG Work Window
SW-MOV-651 Maintenance Protected Equipment Program
Tracking Form
January 20,
2018
Miscellaneous Documents
Number
Title
Revision/Date
SWBP A Replacement Protected Equipment Program
Tracking Form
January 8,
2018
SWBP D Maintenance Window Protected Equipment
Program Tracking Form
January 16,
2018
11-198
Cooper Nuclear Station Service Water System Analysis
Procedures
Number
Title
Revision
0-CNS-WM-104
On-Line Schedule Risk Assessment
0-CNS-WM-
104A
On-Line Fire Risk Management Actions
0-PROTECT-
EQP
Protected Equipment Program
2.1.1
Startup Procedure
190
2.1.10
Station Power Changes
114
2.1.4.3
Power Reduction to <25/30%
2.2.68.1
Reactor Recirculation System Operations
2.2.71
Service Water System
2
2.3_A-4
Annunciator Response Procedure - Panel A-4
7.0.1.7
Troubleshooting Plant Equipment
Condition Reports (CR-CNS-)
2018-00138
2018-00291
2018-00292
2018-00328
2018-00341
2018-00342
2018-00352
2018-00371
2018-00375
2018-00376
2018-00377
2018-00461
2018-00541
2018-00657
2018-00658
2018-01597
2018-01649
Work Orders
5145546
5167094
5167469
5167606
5175025
201054
201413
203083
213083
231297
71111.15 - Operability Determinations and Functionality Assessments
Miscellaneous Documents
Number
Title
Revision
CNS Inservice Testing Basis Document
Failure Modes and Effects Analysis - SW-TE-387B
Indicated Flow with SW-MOV-651MV Closed
2036
Reactor Building Service Water System, Sheet 1
A3
2036
Control Building Service Water System, Sheet 4
PAD 121987
Process Applicability Determination for Isolation of REC
Division 2 SW Flow Path
Procedures
Number
Title
Revision
6.2SW.101
Service Water Surveillance Operation, Div 2 (IST)
Condition Reports (CR-CNS-)
2017-03717
2017-05742
2017-05797
2017-05819
2017-06869
2018-00007
2018-00122
2018-00142
2018-00182
2018-00299
2018-00342
2018-00354
2018-00362
2018-00459
2018-00461
2018-00538
2018-01621
2018-01644
2018-01651
Work Orders
206535
71111.18 - Plant Modifications
Miscellaneous Documents
Number
Title
Revision/Date
2036
Reactor Building Service Water System, Sheet 1
A3
2036
Control Building Service Water System, Sheet 4
EE 2013-04
RHR SWBP FCU 50.59 Inadequate for USAR Change LCR
93-10
LCR 93-0010
Specify a Summer Design Temperature of 131°F for the
RHR SWBP Room
February 5,
1993
Miscellaneous Documents
Number
Title
Revision/Date
NEDC 92-063
Maximum SWBP Room Temperatures w/ No Cooling From
Control Bldg HVAC
NEDC 92-064
Transient Temperature Rise in SWBP Room After Loss of
Cooling
3C2
PAD 121987
Process Applicability Determination for Isolation of REC
Division 2 SW Flow Path
TCC-5231919
Temporary Configuration Change - Replacement of
SW-V-126 With Blind Flange Spool Piece
UCR 98-019
USAR Change Request: SWBP Fan Coil Unit Description
Removal
April 28, 1998
Procedures
Number
Title
Revision
2.2.71
Service Water System
2
2.3_R-1
Panel R - Annunciator R-1
17, 18
7.3.50.4
SW-650MV and SW-651MV Flow Adjustment
Condition Reports (CR-CNS-)
2017-06120
2017-06196
2017-06241
2017-07601
2018-00342
2018-00362
2018-00461
Work Orders
231297
231480
232377
71111.19 - Post-Maintenance Testing
Drawings
Number
Title
Revision
454223426
Emergency Diesel Generator Composite Control Air
Schematic
Miscellaneous Documents
Number
Title
Revision
11445276
Notification
IST Reference/Acceptance Limits Data File
246
Procedures
Number
Title
Revision
2.2.20.1
Diesel Generator Operations
69, 70
6.1DG.101
Diesel Generator 31 Day Operability Test (IST)(DIV 1)
6.1HV.602
Air Flow Test of Fan Coil Unit HV-DG-1C (DIV 1)
6.1SWBP.101
RHR Service Water Booster Pump Flow Test and Valve
Operability Test (DIV 1)
6.2HV.603
Air Flow Test of Fan Coil Unit for FC-R-1H (Div 2)
6.2SW.101
Service Water Surveillance Operation Div 2 (IST)
6.SW.102
Service Water System Post-LOCA Flow Verification
7.0.5
CNS Post-Maintenance Testing
7.0.8.1
System Leakage Testing
7.3.50.4
SW-650MV and SW-651MV Flow Adjustment
14.17.1
DG-1 Annual Calibration
14.28.1
Service Water System Instrument Calibration
Condition Reports (CR-CNS-)
2016-07426
2018-00388
2018-00342
2018-00425
2018-00461
2018-00521
2018-00711
2018-00715
2018-00751
2018-00765
2018-01714
2018-01715
Work Orders
4832440
5145546
5145577
5167078
5167385
5167606
5167617
5169763
5169764
5169985
5184976
5188894
201054
201413
231297
231480
71111.20 - Refueling and Other Outage Activities
Procedures
Number
Title
Revision
2.1.4
Normal Shutdown
157
6.RCS.601
Technical Specification Monitoring of RCS
Heatup/Cooldown Rate
71111.22 - Surveillance Testing
Miscellaneous Documents
Number
Title
Revision/Date
List of Drywell Possible Leak Sources
January 23,
2018
Summary of Primary Containment Sample Results for
Current Fuel Cycle
February 2,
2018
EC 18-003
6.LOG.601 Revision to Address Effects of Voiding on
Drywell Floor Drain Sump Flow Indication
0, 1
Procedures
Number
Title
Revision
6.DWLD.301
Drywell Floor Drain Sump Flow Measuring System
Functional Test
6.DWLD.302
Drywell Floor Drain Sump 1F Flow Loop Channel
Calibration
6.LOG.601
Daily Surveillance Log - Modes 1, 2, and 3
130, 131, 132
6.RCIC.102
6.RR.601B
RRMG B Positioner Maintenance and Setting Electrical and
Mechanical Stops
6.1DG.101
Diesel Generator 31 Day Operability Test (IST)(DIV 1)
15.SUMP.101
Sump Pump Operability Test
Drywell Leakage
Condition Reports (CR-CNS-)
2012-07093
2017-06119
2017-06820
2018-00123
2018-00127
2018-00310
2018-00336
2018-00340
2018-00436
2018-00905
2018-00907
Work Orders
5047898
5099572
5101207
5103351
5114307
5115900
23387
5167175
5177984
5190520
231292
71114.04 - Emergency Action Level and Emergency Plan Changes
Miscellaneous Documents
Number
Title
Revision
Cooper Nuclear Station Emergency Plan
EPIP 5.7.1
Emergency Classification
71114.06 - Drill Evaluation
Miscellaneous Documents
Number
Title
Revision/Date
DEP Performance Evaluation and Data Collection Form -
Scenario SKL052-52-17
January 23,
2018
EPIP 5.7.1
Emergency Classification
EPIP 5.7.2
Emergency Director EPIP
SKL052-52-17
Licensed Operator Requalification Exam Scenario 17
January 3,
2018
71124.02 - Occupational ALARA Planning and Controls
ALARA Committee Meeting Minutes
Meeting
Title
Date
February
Meeting Minutes
February
2017
August
Meeting Minutes
August 2017
October
Meeting Minutes
October 2017
December
Meeting Minutes
December
2017
ALARA Planning, In-Progress Reviews, and Post-Job Reviews
Number
Title
Date
2016-01
RE29 CRDM Replacements
November 5,
2016
2016-03
RWCU Pump B Replace Power Frame
June 8, 2016
2016-05
RE-29 Refuel Floor Activities
November 5,
2016
2016-12
December
14, 2016
ALARA Planning, In-Progress Reviews, and Post-Job Reviews
Number
Title
Date
2016-23
RR-A Motor, Impeller and Seal
November 6,
2016
2017-01
Spent Fuel Pool Clean-Up Project (Online)
December
11, 2017
Audits and Self-Assessments
Number
Title
Date
LO-2017-0204
Focused Self-Assessment:
Occupational ALARA Planning and Controls
December 1,
2017
Miscellaneous Documents
Title
5-Year CRE Reduction Plan (2018-2022)
RE29 Radiological Post Outage Report
2017 Cooper Nuclear Station ALARA Program
Procedures
Number
Title
Revision
9.ALARA.4
Radiation Work Permits
9.ALARA.8
ALARA Document Control
ALARA Program
9.EN-RP-110-03 Collective Radiation Exposure (CRE) Reduction Guidelines
9.EN-RP-110-04 Radiation Protection Risk Assessment Process
9.EN-RP-110-05 ALARA Planning and Controls
9.EN-RP-110-06 Outage Dose Estimating and Tracking
Radiation Work Permits
Number
Title
Revision
2016-014
Refuel Floor Activities
2016-055
RWCU-P-B Replacement and RWCU-CV11 Inspection
2016-060
Refuel Floor General SWP Work
2016-406
CRDMs Support - Support Work - RWP (NO ENTRY
ALLOWED INTO AN AREA POSTED SWP)
Radiation Work Permits
Number
Title
Revision
2016-506
Under vessel CRDMs Change outs Also Keyway Worker
and RP Under vessel Coverage
2016-523
RR-A Motor and Impeller Replacement in RE29 - SWP
2017-107
2017 SFP Cleanup
Condition Reports (CR-CNS-)
2016-06415
2016-06567
2016-07197
2016-08576
2017-02319
2017-04201
2017-04896
2017-04899
2017-05538
2017-06603
71124.04 - Occupational Dose Assessment
Audits and Self-Assessments
Number
Title
Date
Radiation Protection Program Annual Report
2016
16-05
QA Audit of Radiological Controls
August 10,
2016
LO-2017-0204
Focused Self-Assessment:
Occupational Dose Assessment
December 1,
2017
Miscellaneous Documents
Title
Date
2016 DAW Part 61 Analysis
March 29,
2017
100555-0 National Voluntary Laboratory Accreditation Program (NVLAP)
Certificate for Mirion Technologies
July 1, 2017
Internal Dose Assessment Prospectus
2017
Internal Dose Assessment Prospectus
2018
Multiplication Factor for the Merlin Gerin DMC 2000S (White Paper)
March 22,
2012
Procedures
Number
Title
Revision
9.ALARA.1
Personnel Dosimetry and Occupational Radiation Exposure 47
9.ALARA.13
Radiation Worker and Tour Group Dosimetry Management
Procedures
Number
Title
Revision
Radiological Control
Personnel Contamination
9.EN-RP-110-05 ALARA Planning and Controls
Alpha Monitoring
Dose Assessment
Prenatal Monitoring
Dosimeter of Legal Record Quality Assurance
Whole Body Counting and In-Vitro Bioassay
Area Monitoring Program
Self-Reading Dosimeters
9.RADOP.1
Radiation Protection at CNS
9.RADOP.5
Airborne Radioactivity Sampling
Condition Reports (CR-CNS-)
2016-01718
2016-04881
2016-07077
2017-04996
2017-05538
71151 - Performance Indicator Verification
Procedures
Number
Title
Revision
Performance Indicator Process
5C2
71152 - Problem Identification and Resolution
Miscellaneous Documents
Number
Title
Revision/Date
3059
EE-PNL-DG1 125VDC Load & Fuse Schedule, Sheet 11
3059
EE-PNL-DG2 125VDC Load & Fuse Schedule, Sheet 12
EE 2018-001
Characterization of Potential Risk of EDG Indicating Light
Failure
0, 1
G5-262-743
Emergency Diesel Generator #1 Electrical Schematic
Sheet 1
Miscellaneous Documents
Number
Title
Revision/Date
G5-262-743
Emergency Diesel Generator #2 Electrical Schematic
Sheet 1
NPP-61852
Failure Analysis of a Lamp Assembly
November
27, 2017
PAD 121981
Process Applicability Determination - Caution Order:
DG-1-DG-SW-DG2(43CM) Green Ind
PAD 121982
Process Applicability Determination - Caution Order:
DG-1-DG #1 Bulb Control
Condition Reports (CR-CNS-)
2017-01168
2017-05434
2017-05456
2017-06219
2017-07078
2017-07513
2018-00124
2018-00125
2018-00685
2018-00832
2018-01281
Work Orders
26885
71153 - Follow-up of Events and Notices of Enforcement Discretion
Procedures
Number
Title
Revision
2.0.5
Reports to NRC Operations Center
NRC Request for Information
System: Emergency Diesel Generators, Divisions 1 and 2
CD Date Requested by: January 2, 2018
Date Range of Document Request: December 31, 2015 - Current
Please provide the following documents:
1. Copies of all root and apparent cause evaluations performed on this system.
2. Summary list of all condition reports written on this system, sorted by CR classification
3. List of all surveillances performed on this system, sortable by component if possible.
4. Provide copies of the three most recently completed quarterly surveillances for both
divisions
5. List of all corrective maintenance work orders, with description of work, performed on this
system
6. Provide a list of control room deficiencies associated with this system
7. Copies of ODMIs, OWA/OWBs, prompt operability evaluations, and standing orders
associated with this system
8. Summarized list of all Maintenance Rule equipment issues evaluated for the system,
(including their conclusions), copies of each MRule evaluation for the system, and the
MRule Basis Document(s) for the system
9. List of all work orders, with description of work, planned for this system within the next year
10. Provide a list and description of overdue PMs, deferred PMs, and PM change requests for
this system
11. Provide copies of maintenance rule functional failure assessmentsregardless of the
resultperformed on these systems. Include CR number for each item on the list.
2. System design calculations for DG loading capabilities
13. Provide fire impairments associated with this system
14. Provide copies of any QA audits or self-assessments associated with this system
15. Copies of vendor manuals, drawings (P&IDs), and system training manuals
16. System health reports and system engineering logs for this system
17. List and description of temporary modifications; completed ECs (December 31, 2015 -
Current); and planned ECs (within the next year) associated with this system
18. Schedule of activities (Fragnets) for the planned AOT for the Division 1 and 2 DGs
scheduled for the work weeks of 1806 and 1812.
The following items are requested for the
Occupational Radiation Safety Inspection
at Cooper Nuclear Station
(February 12-16, 2018)
Integrated Report 2018001
Inspection areas are listed in the attachments below.
Please provide the requested information on or before January 25, 2018.
Please submit this information using the same lettering system as below. For example, all
contacts and phone numbers for Inspection Procedure 71124.01 should be in a file/folder titled
1-A, applicable organization charts in file/folder 1-B, etc.
If information is placed on ims.certrec.com, please ensure the inspection exit date entered is at
least 30 days later than the onsite inspection dates, so the inspectors will have access to the
information while writing the report.
In addition to the corrective action document lists provided for each inspection procedure listed
below, please provide updated lists of corrective action documents at the entrance meeting.
The dates for these lists should range from the end dates of the original lists to the day of the
entrance meeting.
If more than one inspection procedure is to be conducted and the information requests appear
to be redundant, there is no need to provide duplicate copies. Enter a note explaining in which
file the information can be found.
If you have any questions or comments, please contact John ODonnell at (817) 200-1441 or
john.odonnell@nrc.gov. The other inspector will be Shawn Money.
PAPERWORK REDUCTION ACT STATEMENT
This letter does not contain new or amended information collection requirements subject
to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information
collection requirements were approved by the Office of Management and Budget,
control number 3150-0011.
2.
Occupational ALARA Planning and Controls (71124.02)
Date of Last Inspection:
October 3, 2016
A.
List of contacts and telephone numbers for ALARA program personnel
B.
Applicable organization charts
C.
Copies of audits, self-assessments, and LERs, written since date of last inspection,
focusing on ALARA
D.
Procedure index for ALARA Program
E.
Please provide specific procedures related to the following areas noted below.
Additional Specific Procedures may be requested by number after the inspector reviews
the procedure indexes.
1. ALARA Program
2. ALARA Committee
3. Radiation Work Permit Preparation
F.
A summary list of corrective action documents (including corporate and sub-tiered
systems) written since date of last inspection, related to the ALARA program. In addition
to ALARA, the summary should also address Radiation Work Permit violations,
Electronic Dosimeter Alarms, and RWP Dose Estimates
NOTE: The lists should indicate the significance level of each issue and the search
criteria used. Please provide in document formats which are searchable so that
the inspector can perform word searches.
G.
List of work activities greater than 1 rem, since date of last inspection,
Include original dose estimate and actual dose.
H.
Site dose totals and 3-year rolling averages for the past 3 years (based on dose of
record)
I.
Outline of source term reduction strategy
J.
If available, provide a copy of the ALARA outage report for the most recently completed
outages for each unit
K.
Please provide your most recent Annual ALARA Report.
4. Occupational Dose Assessment (Inspection Procedure 71124.04)
Date of Last Inspection:
March 23, 2016
A.
List of contacts and telephone numbers for the following areas:
1. Dose Assessment personnel
B.
Applicable organization charts
C.
Audits, self-assessments, vendor or NUPIC audits of contractor support, and LERs
written since date of last inspection, related to:
1. Occupational Dose Assessment
D.
Procedure indexes for the following areas:
1. Occupational Dose Assessment
E.
Please provide specific procedures related to the following areas noted below.
Additional Specific Procedures will be requested by number after the inspector reviews
the procedure indexes.
1. Radiation Protection Program
2. Radiation Protection Conduct of Operations
3. Personnel Dosimetry Program
4. Radiological Posting and Warning Devices
5. Air Sample Analysis
6. Performance of High Exposure Work
7. Declared Pregnant Worker
8. Bioassay Program
F.
List of corrective action documents (including corporate and sub-tiered systems) written
since date of last inspection, associated with:
1. National Voluntary Laboratory Accreditation Program (NVLAP)
2. Dosimetry (TLD/OSL, etc.) problems
3. Electronic alarming dosimeters
4. Bioassays or internally deposited radionuclides or internal dose
5. Neutron dose
NOTE: The lists should indicate the significance level of each issue and the search
criteria used. Please provide in document formats which are searchable so that
the inspector can perform word searches.
G.
List of positive whole body counts since date of last inspection, names redacted if
desired
H.
Part 61 analyses/scaling factors
I.
The most recent NVLAP accreditation report or, if dosimetry is provided by a vendor, the
vendors most recent results
SUNSI Review
By: CHY/rdr
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available
Keyword:
OFFICE
ASRI:DRP/C
RI:DRP/C
BC:DRS/EB1
BC:DRS/EB2
BC:DRS/OB
BC:DRS/PSB2
NAME
RKumana
MStafford
TFarnholtz
JDrake
VGaddy
HGepford
SIGNATURE
/RA/
/RA/
/RA/
/RA/
/RA/
/RA/
DATE
4/23/18
4/23/18
04/23/2018
4/23/2018
4/24/18
4/23/18
OFFICE
TL:DRS/IPAT
SPE:DRP/C
BC:DRP/C
NAME
GGeorge
CYoung
JKozal
SIGNATURE
/RA/
/RA/
/RA/
DATE
4/24/2018
4/27/2018
5/08/2018